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An Overview of Approach to Corrosion Issues in Fukushima Daiichi Nuclear Power Station

机译:福岛Daiichi核电站腐蚀问题概述

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The earthquake of magnitude 9.0 occurred on March 11, 2011 and the following tsunami caused the loss of ability to cool fuel in the reactors and the spent fuel pools (SFPs) in the Fukushima Daiichi nuclear power station. Since seawater was temporarily injected into the reactors and the SFPs to cool the fuel as an emergency action, various corrosion issues emerged. Temperatures in the reactors of Unit 1 to 3 exceeded 100 °C just after the accident and then decreased gradually to below 50 °C. The salt concentration in reactor water was assumed to be high due to seawater boiling down. In terms of keeping the stability of fuel cooling and the integrity against aftershocks, mitigating corrosion of carbon steel became a primary issue for the reactors. So far, the following corrosion mitigation measures have been applied to the reactors; (a) decreasing temperature, and deoxidization and sterilization (b) by deaeration of feed water, (c) by nitrogen gas injection into the reactors, (d) by hydrazine injection to cooling water, and (e) desalination of cooling water. The temperatures of SFP water in Unit 1 to 4 were from 47 to 93 °C just after the accident and then decreased to below 40 °C. The water quality corresponded to diluted seawater containing up to 2000 ppm Cl~-. However, pH at Unit 3 showed strong alkaline due to fallen concrete rubble. Examples of corrosion risks were localized corrosion of stainless steel pool liners and galvanic corrosion and alkaline corrosion of fuel racks made of Aluminum. Besides (a), (b), (d), and (e) listed above, (f) pH control have been applied to the SFPs for corrosion mitigation. Although cooling water quality have been improved to be equivalent of tap water at less than 50 °C, some corrosion issues remain to be solved in terms of long-term integrity.
机译:幅度为9.0的地震发生于2011年3月11日,下面的海啸导致福岛帝茶核电站中冷却燃料燃料和福岛核电站的燃料池中的能力。由于海水被暂时注入反应器和SFP以使燃料冷却作为紧急行动,因此出现了各种腐蚀问题。在事故发生后,单位1至3的反应器中的温度超过100°C,然后逐渐降低至50℃以下。由于海水沸腾,反应器水中的盐浓度被认为是高的。在保持燃料冷却的稳定性和对余震的完整性的方面,减轻碳钢的腐蚀成为反应器的主要问题。到目前为止,对反应堆应用了以下腐蚀缓​​解措施; (a)通过氮气注射到反应器中的氮气注射到冷却水中,通过氮气注射到电反应器中的氮气注射,(c)通过氮气注射到冷却水中的氮气注射,(d)降低,并通过氮气注射脱氧和灭菌(b)。在事故发生后,单位1至4中的SFP水的温度为47至93°C,然后降低至低于40℃。水质对应于含有高达2000ppm的稀释海水〜 - 。然而,由于混凝土瓦砾,第3单元的pH显示出强烈的碱性。腐蚀风险的实例是不锈钢池衬垫的局部腐蚀,以及由铝制成的燃料架的电流腐蚀和碱性腐蚀。此外,除了(a),(b),(d)和(e)上方,(f)pH控制已应用于SFP以进行缓解缓解。虽然冷却水质量得到改善为等同于小于50°C的自来水,但在长期完整性方面仍有一些腐蚀问题。

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